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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
Volkan Seker, Haining Zhou, Thomas J. Downar
Nuclear Technology | Volume 206 | Number 6 | June 2020 | Pages 805-824
Technical Paper | doi.org/10.1080/00295450.2019.1703464
Articles are hosted by Taylor and Francis Online.
The Transient Reactor Test Facility (TREAT) was designed in the late 1950s to test nuclear fuels and materials under extreme conditions and has been recently restarted by the U.S. Department of Energy to provide the transient test capability to evaluate the performance of innovative nuclear fuels under accident conditions. Benchmark experiment data are required to support the operation of TREAT and to validate the computational analyses necessary to design and evaluate the experiments. Therefore, in this paper, benchmark problems based on the minimum critical (MC) core and M8 Power Calibration Experiment (M8CAL) core of TREAT were developed and analyzed using the Monte Carlo code Serpent. The eigenvalue, temperature coefficient, and flux distributions for both the MC core and the M8CAL cores were calculated and compared to the experimental data. All the calculated values compared well to the experimental data, and both problems were subsequently approved as International Reactor Physics Experiment Evaluation Project benchmarks.